ML20245K915
| ML20245K915 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 06/27/1989 |
| From: | Bjorgen J, Hare E, Jordan M, Mcghee J, Parrish M, Mary Spencer NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20245K904 | List: |
| References | |
| 50-254-OL-89-02, 50-254-OL-89-2, NUDOCS 8907050299 | |
| Download: ML20245K915 (68) | |
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U.S. NUCLEAR' REGULATORY COMMISSION REGION III Report No. 50-254/0L-89-02 Docket No. 50-254' License No. DPR-29 I . Licensee: Commonwealth Edison P.O. Box 767 Chicago, IL 60690 Facility Name: Quad Cities Nuclear Power Station-Examination Administered At: Morris Simulator . Morris Illinois r ' Quad Cities Nuclear Power Station Cordova, Illinois Examination Conducted: May 11-13, 15, 16, 1989 O
NRC Examiners:
E. Hare d M E C b u .
Date J. McGhee c # ON -
Date.
M. Parrish M M b .Date M. Spencer #
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~# (O 97 Date Chief Examiner: J. Bjorgen - Af M Approved By: Michael J. Jordan 7 i
Examination Summary Examination administered on May 11-13, 15, 16, 1989 (Report No. 50-254/0L 02))~
Written and operating requalification examinations were administered to nine Senior Reactor Operators (SRO) and three Reactor Operators (RO). In conjunction with the simulator' portion'of these examinations,.two shift and one non-shift crews were evaluated.
Results: The.NRC. passed all crews and individuals in all portions of the examination except one Reactor Operator that failed the written examination.
The facility results matched the NRC results. While the requalification program has been assigned an.overall rating of satisfactory, two programmatic l weaknesses,were identified (see Paragraph 4).
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REPORT DETAILS
- 1. Examiners J.;Bjorgen, Chief Examiner E. Hare M. Parrish J. McGhee M. Spencer
- 2. Exit Meeting An exit meeting was conducted on May 17, 1989. A followup telephone conference call was also conducted on June 21, 1989 between Mr. J. Sirovy, Commonwealth Edison Czpany, and Mr. G. Wright, NRC, to discuss .the final evoluation results. The following people were in attendance at the May 17, 1989 meeting:
Commonwealth Edison Company Representatives R..Bax, Station Manager J. Sirovy, Services Director J. Swales, Operating Assistant Superintendent J. Kopacz, Operating Engineer J. Neal, Training Supervisor M. Rodts, Operator Training Group Leader D. Boyles, Instructor R. Svaleson, Instructor L. Davis, Director Operations Training - Production Training Center W. Graham, Simulator Supervisor - Production Training Center T. Barber, Regulatory Assurance NRC Representatives M. Jordan, Section Chief, Operator Licensing Section 1 J. Bjorgen, Chief Examiner E. Hare, Examiner R. Higgins, Senior Resident Inspector The following items were discussed during these meetings.
j 1. Examination Material The facility supplied requalification examination material was found to be unsuitable for implementation when initially reviewed by the NRC in March 1989. Considerable rework was required to clarify critical steps, to add valid facility based references to the written exam questions and job performance measures, and to obtain functional dynamic simulator scenarios. Due to the exam schedule constraints the rework effort was limited to those portions of the material selected for the actual exam.
While the exam was successfully completed considerable rework is required for the remainder of the facility requalification exam material. The E_-
f scope of the rework _was discussed with the facility personnel in detail.
The quality of the examination material was identified as a programmatic weakness. The facility was requested to pt , vide the NRC with a proposed schedule for upgrading the examination material to support future requalification examinations.
- 2. Dynamic Simulator Examinations The following items were noted during the conduct of the Dynamic i Simulator examinations.
- a. The facility used contractor evaluators and simulator operators during the dynamic simulator portion of the examination. Several weaknesses were noted with this process as follows:
(1) More than one simulator operator was used during the examination. These operators had not participated in the examination verification conducted two weeks prior to the i examination. As a result some of the simulator scenarios were '
not run as the examination team anticipated. In at least '
one case reactor water level took much longer to degrade than expected because the High Pressure Coolant Injection System was allowed to run for an excessive amount of time.
(2) More than one contractor evaluation team was also used during the examination. This lead to inconsistent evaluations being given to the three crews being examined. For example, one crew was praised for isolating the main feedwater system when i' condenser hotwell level reached the low level limit, while another crew continued to feed the reactor vessel with an empty hotwell (due to a simulator modeling problem) with no negative comment by the evaluators. Other examples were discussed with the facility training department representatives.
(3) The facility training and operations representatives provided minimal participation during the crew debriefings throughout the simulator examinations. This detracted from the overall quality of the crew evaluations since the contractor evaluators cannot be expected to convey the facility training and l operating philosophy. ;
- 3. Examination Results Comparison A comparison of the examination results between the facility and the NRC i I
grading found very consistent results.
- 4. Requalification Programmatic Weaknesses 1
The items identified in paragraphs 1 and 2 above are considered ;
programmatic weaknesses. The facility was requested to submit a j corrective action plan to the NRC by the enclosed cover letter.
- 5. Overall Requalification Program Evaluation The requalification program has been assigned an overall program rating of satisfactory. The evaluation criteria of NUREG-1021 was met. l 3
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Facility: Quad Cities.' Nuclear Power Station Examiner: J. Bjorgen Dates of Evaluation: May 11-13, 15, 16, 1989 Areas Evaluated: Written Oral Simulator Examination Results:
R0 SR0 Total Evaluation Pass / Fail Pass / Fail Pass / Fail (S, M, or U) ,
Written Examination 2/1 9/0 11/1 S Operating Examination Oral 3/0 9/0 12/0 S Simulator 3/0 9/0 12/0 S Evaluation of facility written examination grading.
The facility grading closely matched the NRC grading.
Crew Examination Results Crew 1 Crew 2 Crew 3 Evaluation Pass / Fail Pass / Fail Pass / Fail (S,M,orU)
Operating Examination Pass Pass Pass S Overall Program Evaluation Satisfactory RI RII RIII
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. QUAD CITIES STATION REQUALIFICATION QUESTION / ANSWER SHEET Point Value: 2.40 Question # 215004 C-1 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> after a reactor scram from full power, with reactor water temperature at 327 F, a reactor start-up is initiated. Following a peripheral rod withdrawal of one notch while in the source range, the following conditions occur:
- The NSO observes a rapid change in reactor period to 19 seconds and an increasing count rate on all operable SRMs.
- The following alarms are received:
SRM HI OR INOP SRM SHORT PERIOD ROD WITHDRAW BLOCK
- a. What is the most likely cause for this' condition? (1.2)
- b. What operator action should be performed to terminate the rapid increase in reactor power. (1.2) _, _
AFSWER:
- a. This is due to the changing Xenon concentration during this hot start-up (0.6) combined with zero voids and hot temperature (0.6).
GMWW MJVrrVETf&CYCbO'- 1 b.
"nW Insert control rods
REFERENCES:
QGP 1-1, Normal Unit Start-up, Rev 42, page 5 QOA 400-1, Reactivity Addition, Rev 5 QGP 1-2, Unit Start-up to Hot Standby, Rev. 21, page 4 QGP 1-3, Unit Hot Standby to Power Operation, Rev. 28, page 2 OBJECTIVES:
TASK XREF: 215-01-01 005 Monitor the Nuclear Instrumentation System. ,
344-03-02-022 Direct Shift Personnel Actions ~to ensure l Plant Safety During Abnormal Events.
K/A XREF: 215004 A2.04 3.5/3.7 SG-1 3.6/3.9 SG-8 3.5/3.4 ..
EST TIME: 4.6 minutes l .-_--_______ -
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- i. COMMONWEALTH EDISON COMPANY QUAD CITIES STATION
- REytfALIFICATION QUESTION / ANSWER SHEET.
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Point Value: 2.25 ,
Question # 201002 C-2' QUESTION:
A. reactor start-up is in progress from a scram that occurred six hours earlier. ' Plant parameters are as follows: -i Reactor pressure: 845 psig Recire. pumps: 30% speed Reactor power: 30 on range 4 of IRMs Rod array: 7A Rod step: 18 The current. step of rods are being moved from position 12 to position 48.
The Qualified Nuclear Engineer (QNE) monitoring rod movement in-the control room recommends using notch override-for all withdrawals due to the competi tion with ' the increasing Xenon concentration.
Explain whether this type of movement is allowable. (2.25) __-
ANSWER:
At this point notch over' ride is only allowable between positions 24 and
- 48. Notch override may be used during these positions but must be notch moved from 12 to 24 (2.25)
OR Notch override may not be used between positions 00 and 24 until reactor pressure is greater than 920 psig with 1 bypass valve partially open. (2.25)
REFERENCE:
QGP 1-1, Rev 43 page 5 )
QOP 280-1, Rev 6 OBJECTIVE:
TASK XREF: 201-01-01-008, Operate the control rods using " notch" override.
341-03-02-014, Direct shift personnel actions during major plant evolutions. ,,
K/A XREF: 201002 SG-1 3.8/3.8 SG-10 3.9/3.9 l EST TIME: 4.3 minutes b.
COMMONWEALTH EDISON COMPANY QUAD CITIES STATION REQUALIFICATION QUESTION / ANSWER SHEET Point Value: 2.50 Question # 256000 G-1 QUESTION:
With the reactor normally-operating at near rated power a rupture occurs on the condensate transfer system. The leak is isolated, but not until CCST water levels drop to 8 feet. The operating crew is informed that it will take approximately 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> before level in the CCSTs can'be restored.
i
- a. STATE what actions, if any, are required to be performed on the RCIC and HPCI systems until CCST water level is restored and 3 why? (1.25) 0 25) 4
- b. """ era thace eerien: requir:d? '1.25) i ANSWER:
- a. The jockey fill system can be aligned to the HPCI and RCIC and_ the suctions of the HPCI and RCIC pumps must be aligned (within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) to take a suction from the torus (0.65). The systems must be vented from their high point vents and water flow observed at least every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(0.6)
- b. Filled discharge piping for HPCI and RCIC systems are ensured by maintaining the level in the Contaminated Condensate Storage Tank at or above 9.5 feet. (1.25)
REFERENCE:
TECHNICAL SPECIFICATIONS, sections 3.5.G.3/4.5.G.3 QOA 900-3 A-12(71), Low CST level, Rev.13 l OBJECTIVE:
TASK XREF: 341-03-02-018 Apply Technical Specifications Directions for Safety Limits, Safety System Settings and Limiting Conditions for Operation 299 03-01-015 Apply Technical Specification Requirements K/A XREF: 256000 SG-11 3.1/3.9 SG-15 3.7/3.8 EST TIME: 4.8 minutes kh }he qc.s k was * 'bk'm rikrak Si h %rn, the Nr "pW 4001 RftAh$ GE
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QUAD CITIES STATION REQUALIFICATION QUESTION / ANSWER SHEET Point Value: .1.95 Question # 239002 C-3
. QUESTION:
The unit 2 is at approximately.500 MWe with surveillance in progress. I The' SCRE reports that QOS 201-1 has just been completed and that the
' relief valve 3A (Target Rock) is inoperable since the valve'would not open during this surveillance.
Describe what effect this inoperable component'has on the continued plant operation, INCLUDE any applicable power limitations and time restraints.
(1.95) ;
-ANSWER:
An orderly shutdown should be initiated. The reactor coolant pressure shall be below 90 psig and the coolant temperature should be below 320 F within 24 hrs. (1.95) _,
REFERENCE:
TECHNICAL SPECIFICATIONS, Section 36.E.2, Amendment no. 114 QOS 201-1, MANUAL OPERATION OF ELECTROMATIC RELIEF VALVES rev.11 QOS 201-3, SAFETY VALVE INOPERABLE OUIAGE REPORT PAGE 3 OBJECTIVES:
TASK XREF: 299-03 01 015, Apply Technical Specification Requirements.
341-03-02-018, Apply Technical Specification directions for safety limits, safety system settings and limiting conditions for operations.
K/A XREF: 239002 SG-2 3.1/3.9 SG-11 3.5/4.0 EST TIME: 3.7 minutes l
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QUAD CITIES STATION REQUALIFICATION QUESTION / ANSWER SHEET l
Point Value: 2.25 QUESTION # 295015 C-2 QUESTION:
Unit 2 plant is in an outage with its CRD hydraulic system dismantled for pipe replacement work.
Unit 1 plant has just experienced a transient from fu11' power. Half of all the control rods are still at positions greater than 04. Reactor power indicates approximately 8%. Reactor water level is between +8 and
+48 inches and stable. RPV pressure is less than 1040 psig and is being controlled with bypass valves. All SRVs are operable, but none are expected to open -in response to this transient. ~
The blue scram lights are illuminated on the full core display.
The rods cannot be scrammed with reactor pressure and the scram cannot be reset. The running CRD pump trips, and cannot be restarted. The other CRD pump also trips when it is started.
How can the control rods be inserted into the reactor core? (2.25)..
ANSWER:
Individually direct effluent from 301-119 for rod to be inserted to a Rad Waste drain and open 301-119 (withdrawal line vent). (2.25)
REFERENCE:
QGA 100-1, RPV LEVEL CONTROL Rev. 3 QGA 100-3, RPV POWER CONTROL Rev. 2 QGA 500-7, LEVEL / POWER CONTROL Rev. 2 p. 1 1 OBJECTIVE: LIC-PROC Rev. 1 Obj. # 2 TASK XREF: 200-05-01-020, Recognize and respond to Failure of reactor j to scram when required or failure of control rods to fully ;
insert during scram.
344-03-02-007, Direct shift personnel actions to ensure plant safety during abnormal conditions.
K/A XREF: 295015 AK2.01 3.8/3.9 AK2.07 3.3/3.4 AA1.01 3.8/3.9 SG-11 4.2/4.4 EST TIME: 4.3 minutes !
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COMMONWEALTH EDISON COMPANY QUAD CITIES STATION REQUALIFICATION QUESTION / ANSWER SHEET POINT VALUE: 3.85 Question # 212000 C-1 QUESTION:
I The reactor is operating.at near rated thermal power with the following conditions:
- APRM channel 6 is bypassed
- IRM channel 17 is bypassed
- IRM channel 12 is bypasseo
- SRM channel 21 is bypassed While bypassing a failed level D LPRM assigned to APRM channel 3, the operator notices that-only one D level LPRM assigned to that channel is remaining as unbypassed for APRM 3.
Describe what actions should be taken, with regards to the Reactor Protection System, for this situation. Include in your answer, operator actions and surveillance requirements. (3.85)
ANSWER:
A half scram must be taken on RPS channel "A". (1.925) Functionally test all other RPS instruments that monitor the same parameter within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
(1.925)
REFERENCE:
Quad Cities Technical Specifications, Table 3.1-3 QOS 500 OBJECTIVE:
TASK XREF: 212-01-01-002, Place a reactor protection channel in the ;
tripped condition. l 341-03-02 018, Apply Technical Specifications directions for Safety Limits, Safety System Settings and Limiting ;
Conditions for Operation.
K/A XREF: 212000 A2.03 3.3/3.5 A2.04 3.5/3.7 A4.01 4.6/4.6 i EST TIME: 7.4 minutes q
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. QUAD CITIES STATION REQUALIFICATION QUESTION / ANSWER SHEET Point Value: 2.10 Question # 295003 C-4 QUESTION:
During normal plant operations at near rated power, bus 18/19-5 is lost due to an electrical fault. The following loads are supplied by MCC 18/19-5:
- Control room return air fan
- 202-4A Recire pump suction valve 202-4B Recire pump suction valve
- 202-5A Recire pump discharge valve
- 202-5B Recirc pump discharge valve
- 202-6A Recire loop equalizing valve k
- 202-6B Recire loop equalizing valve f
- 202-9A Recire loop equalizing bypass valve !
- 202-9B Recire loop equalizing bypass valve
- 1001-28A RHR outboard shutoff valve "
- 1001-28B RHR outboard shutoff valve
- 1001-29A RHR inboard shutoff valve _,.
- 1001-29B RRR inboard shutoff valve What Technical Specifications limitations apply in order to continue with plant operations if bus 18/19-5 can not be restored? (2.10)
ANSWER:
Continued reactor operation is permissible for 7 days (0.42) provided both core spray subsystems (0.42), the containment cooling mode of RHR (0.42) and the emergency diesel generators required for operation of such components if no external source of power were available (0.42) and operable (0.42).
REFERENCE:
Technical Specifications, section 3.5.A.5, page 3.5/4.5-3 4E-1312, Reactor Building Essential Service 480V MCC Key Diagram for 18-1B, 19-4, 18/19-5, & 19-6 OBJECTIVE:
TASK XREF: 299-03-01-015 Apply Technical Specification Requirements 341-03-02-018 Apply Technical Specification Directions.for Safety Limits, Safety System Settings and Limiting Conditions for Operations K/A XREF: 2995003 SG-3 3.2/4.1 AK2.04 3.4/3.5 EST TIME: 4 minutes f i
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COMMONWEALTH EDISON COMPANY QUAD CITIES STATION REQUALIFICATION QUESTION / ANSWER SHEET Point Value: 3.35 Question # 295026 C-1 QUESTION:
While controlling RPV pressure at.about 1009 psig with the ADS valves following a reactor scram, the. operator observes that torus. temperature is indicated to be 149 F and torus water level is reading 12 ft. What ACTION is required for this situation and STATE why this action must be taken?- (3.35) r ANSWER:
(The operator must enter QGA 500-2 and) Emergency Depressurize the reactor (1.675). .This is required because the HCLL has been exceeded (The HCLL is
. based on the ability of the torus to accept additional heat input without unstable (complete) stearn condensation) (1.675).
REFERENCE:
QGA 200-4, Suppression Pool Level Control, Rev 2 OBJECTIVE:
TASK XREF: 299-03-01-009 Report Abnormal Parameters or Conditions 344-03-02-024 Direct Corrective-Actions to Mitigate the Consequences of the Emergency Event K/A XREF: 295026 SG-11 4.4/4.6 SG-7 3.4/3.8 EST TIME: 6.4 minutes 1
COMMONWEALTH EDISON COMPANY QUAD CITIES STATION i REQUALIFICATION QUESTION / ANSWER SHEET l
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l Point Value: 3.35 Question # 295028 C-1 ]
l QUESTION: ]
i The reactor is at 100% power. Due to an inoperative drywell cooler, the I drywell temperatures have been steadily increasing. Drywell pressure is increasing at a slower rate and is 1.45 psig. The temperature indicated by the process computer for computer point C166 is 168 F. The sensor ]
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for that computer point then fails. After a time delay, the control room '
operator recognizes the failure.
i The current value of selected indicators are as follows:
The average of point 9 on recorders 1640-200 A and B 87 F (Torus Water Temperature)
Valve Leak Recorder 1-260-20 pt 19 175.7 F (Drywell Air Temperature)
Drywell Environs Indicator 5741-170 pt 36 174.9 F !
(Drywell Air Temperature)
The current value of selected process computer parameters are as fhllows:
Point C165 180.8 F Point C169 88.6 F Point C170 85.2 F State any QGA procedures that must be entered, and why, and any operator actions that must be accomplished to deal with the current drywell temperature.
i ANSWER: -
Enter the QGA 200 block. (200-1) (0.8375)
Continue monitoring Drywell Temperature. (0.8375)
Operate available drywell cooling. (0.8375)
Because process computer point C165 indicates above 180 F. (180 degrees drywell temperature is a 200 block entry condition) (0.8375)
REFERENCE:
QGA 00, QGA Manual Preface Rev. 7 p. 2 **
QGA 200-1, SUPPRESSION POOL TEMPERATURE CONTROL Rev. 2 QGA 200-2, DRYWELL TEMPERATURE CONTROL Rev. 2 OBJECTIVE:
TASK XREF: 344-03-02-024, Direct corrective actions to mitigate the consequences of the emergency event.
K/A XREF: 295028 EK3.04 3.6/3.8 SG-11 4.2/4.4 EA2.01 4.0/4.1 EST TIME: 6.4 minutes L_______ __ __
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COMMONWEALTH EDISON COMPANY QUAD CITIES STATION REQUALIFICATION QUESTION / ANSWER SHEET POINT VALUE: 3.10 Question # 212000 C-2 QUESTION:
With the reactor operating at 85% of rated thermal power, approximately thirty minutes earlier a fire occurred in the B RPS MG set. Since then, all appropriate actions for the fire have been taken. At this time, the RPS bus is re-energized frem its reserve power supply and the NSO attempts to reset the half-scram. After operating the scram reset switch, the NSO reports that the half-scram did not reset and that all alarms associated with the B RPS channel and the scram discharge volume level have cleared ,
except for; j 90X-5-A-14 CHANNEL A/B DISCH VOLUME HIGH LEVEL
- a. Explain what operations or conditions will have to be accomplished or met in order to reset the half-scram in this situation. (1.04)
- b. When discussing the situation, the NSO suggests placing the SDV High Level Bypass keylock switch in Bypass in order to allow the half-scram to be reset. Explain why this is, or is not, a valid method to use in this situation. (2.06)
ANSWER:
- a. The SDV heaters must be warmed back up before the half-scram can be reset. (1.04)
- b. This is not a valid method (1.03), since the SDV High Level Bypass keylock switch does not bypass this trip in the RUN mode.
(Only bypass the-high level trip signal if the reactor mode switch is in the Shutdown or Refuel position.) (1.03)
REFERENCE:
QOA 900-5-B-1, Rev 12 QOA 9000-1, Rev 12, page 5 OBJ ECTIVE:
TASK XREF: 212-01-01-001, Energize the reactor protection system.
212-01-02-001, Energize the reactor protection system.
K/A XREF: 212000 A2.14 3.9/4.0 A2.16 4.0/4.1 **
A3.05 3.9/3.9 A4.04 3.9/3.9 A4.09 3.9/3.8 A4.14 3.8/3.8 EST TIME: 6.0 minutes I
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, f COMMONWEALTH EDISON COMPANY QUAD CITIES STATION l REQUALIFICATION QUESTION / ANSWER SHEET l l
Point Value: 2.60 Question # 223001 S-1 QUESTION:
The plant has been operating normally at 75% power for 3 days when the following alarms are received:
What personnel safety precautions should be taken by the personnel, who are sent to the reactor building basement, to investigate this problem?
(2.60)
ANSWER:
All personnel should wear fresh air packs in the suppression chamb[r area (until the area is released by Rad Protection, pertaining to 0 "**"U 2
and radioactivity.) (2.60)
REFERENCE:
QOA 1600-5, rev. 5 QOA 900-3-A, rev. 13 QOA 900-4-C, rev. 12 QOA 900-4-D, rev. 17 OBJECTIVE:
TASK XREF: 223-01-01-006, Monitor the containment system in standby readiness.
K/A XREF: 223001 A2.11 3.6/3.8 SG 2 3.0/3.9 SG-15 4.1/4.2 EST TIME: 5 minutes
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COMMONWEALTH EDISON COMPANY u -QUAD CITIES STATION' REQUALIFICATION. QUES'iION/ ANSWER SHEET Point Value: 2.60 Question # 295029 C-1 QUESTION:
The plant is undergoing a~ transient. Plant parameters are:
Drywell temperature is 270 F Drywell pressure is 19 psig Torus water level is 19.5 feet Torus pressure is 17 psig Torus water temperature is 165 F RPV water level is +9 inches and increasing Reactor pressure is 385 psig and decreasing Explain why Drywell sprays should not be started to lower Drywell pressure for these conditions. (2.60)
ANSWER;- ,_,..
Torus water level is greater than the level to permit Drywell Spray
-initiation. (2.60)
REFERENCE:
QOA 1000-8, Post Accident Containment Spray rev. 5 p.2 QGA 200-4, SUPPRESSION POOL LEVEL CONTROL rev. 2 OBJECTIVE:
' TASK XREF: 344-03-02-018, Direct shift personnel actions to ensure plant safety during emergency conditions.
K/A XREF: 295029 SG.12 3.6/4.4 SG.11 4.2/4.5 EK1.01 3.4/3.7 EST TIME: 5 minutes t
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REQUALIFICATION QUESTION / ANSWER SHEET l Point Value: 2.50 Question # 201006 C-2 QUESTION:
4 Unit 1 is at the 90% flow control line. Shift change has just been completed and the NSO is about to start withdrawing rods to continue the {
start-up when he notes that the time display on the Rod Worth Minimizer has stopped updating 5 minutes ago. l What action, if any, should be taken due to this discovery? (2.5)
ANSWER:
Steps should be taken to transfer to the other RWM (1.25) or re-initialize the stalled RWM. (1.25) ,
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REFERENCE:
QOP 207-1, NEW ROD WORTH MINIMIZER OPERATION rev.4 hkI OBJECTIVE: -
TASK XREF: 299-03-01-009 Report abnormal parameters or conditions. b p/
341-03-02-051 Interpret / troubleshoot system operation and operability.
K/A XREF: 201006 A3.02 3.5/3.4 SG-1 3.5/3.8 EST TIME: 4.8 minutes l
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4 COMMONWEALTH EDISON COMPANY QUAD CITIES STATION REQUALIFICATION QUESTION / ANSWER SHEET Point Value: 2.75 Question # B202002 C-1 QUESTION:
The reactor plant is being prepared for a start-up. The "A" and "B" recirc pumps have been started and are currently running at approximately 25% speed, in individual manual control.
What operator precaution, with regards to recirculation pump operation, is required for this situation. (2.75)
ANSWER:
An operator must constantly observe the speed indicators to allow recire pump speed to run between 20% and 30%. (2.75)
REFERENCE:
QOP 202-3, REACTOR RECIRCULATION SYSTEM FLOW CONTROLLER OPERATION, Rev. 6, p. 1, step D.1 OBJECTIVE: LIC-0202-1, Rev. 2, Obj . # 12 TASK XREF: 202 01-01-002, Adjust the recirculation flow using manual control.
202 01-01-006 Monitor recirculation pumps in operation.
202-01-02-006 Monitor recirculation pumps in operation.
K/A XREF: 202002 A1.01 3.2/3.2 SG-5 3.3/4.0 SG-10 3.3/3.3 SG-13 3.6/3.4 202001 A1.01 3.6/3.5 SG-1 3.9/3.9 SC-5 3.4/4.2 SG-10 3.5/3.7 EST TIME: 5.3 minutes-l I
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REQUALIFICATION QUESTION / ANSWER SHEET Point Value: 2.85 Question # 204000 C-2 QUESTION:
The reactor water cleanup system is being used for reactor vessel water level control. The RWCU return isolation valve, MO-1201-80 is throttled to maintain the system's discharge pressure 140 psig greater +hri reactor pressure. The NSO has the following indications on control Acca panel 90x-4:
Instrument Egge Indication FI-1290-30A F/D A Flow 65 gpm FI-1290-30B F/D B Flow 65 gpm FI-1290-11 Reject line flow 65 gpm TI-1290-21 RWCU Inlet 400 deg F TI-1290-21 Regen "A" Outlet 300 deg F TI-1290-21 Regen "B" Outlet 300 deg F TI-1290-21 Non Regen Outlet 134 deg F TI-1290-21 Return to Reactor 390 deg F
~
At this time the NSO notices that reactor vessel level has increased to slightly above its desired operating range and is still slowly increasing. The operator decides to increase RWCU blowdown flow by 20 gpm and opens the FCV*1239 to increase the reject rate. The operator also throttles the MO-1201-80 closed to maintain RWCU discharge pressure at 140 psig greater than reactor pressure.
Evaluate the situation and STATE two possible complications which could result from increasing the RWCU system blowdown flow, by throttling open FCV 1239. (setpoints required) (2.85)
ANSWER: -
2.5 Drywell pressure could increase (0.7125) to % psig (0.7125) (due to increasing RBCCW temperatures)
When the nonregerative heat exchanger outlet temperature reaches 140 F (0.7125), the RWCU isolation could occur (0.7125).
REFERENCE:
QOP 1200-7, rev.2, Reactor Water Cleanup System Coolant Rejection, p. 2 -
QOP 1200-8, rev.2, Reactor Water Cleanup System Shutdown OBJECTIVE:
TASK XREF: 204-01-01-008, Operate the Reactor Water Cleanup system to conduct blowdowns.
204-01-01-011, Monitor the Reactor Water Cleanup system.
K/A XREF: 204000 K6.01 3.1/3.3 K4.04 3.5/3.6 Kl.09 3.2/3.3 EST TIME: 5.5 minutes
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COMMONWEALTH EDISON COMPANY )
QUAD CITIES STATION REQUALIFICATION QUESTION / ANSWER SHEET .
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.1 Point Value: 1.90 . Question # 205000 C-1 QUESTION:
The reactor is shutdown and vented, with RHR maintaining reactor coolant !
temperature at approximately 120 F. The Condensate /Feedwater system is Out-of-Service and the CRD system is off. The "A" RHR pump is operating with a total SDC flow of 4200 gpm. Electrical maintenance personnel have been given permission to adjust the limit switches for the MO-1001-34A, Torus Spray / Suppression Pool Cooling outboard isolation valve. Unnoticed by the NSO, the maintenance personnel inadvertently cause the MO-1001-29A, RHR SDC inboard isolation valve, to close by jumpering the wrong contacts. EXPLAIN any reactor level control problems which would result from continued RHR operation with the present valve lineup. (1.9)
ANSWER:
(Abouttenseconds),followingtheclosureoftheRHRSDCinboard-isolation valve (M0-1001-29A), the RHR loop A minimum flow valve (MO-1001-18A) will open (0.95). This condition opens a flow path for draining the reactor vessel to the suppression pool. (0.95) 1 i
REFERENCE:
QOP 1000-5, Shutdown Cooling Start-up and Operation, Rev 14, section D.9 i P & ids M-37(79), RHRS Sheet 1 and M-39(81), RHRS Sheet 2 l OBJECTIVE:
TASK XREF: 205-01-01-008 Monitor the Residual Heat Removal System 205-01-02-008 Monitor the Residual Heat Removal System K/A XREF: 205000 A2.05 3.5/3.7 K3.02 3.2/3.3 A1.05 3.4/3.4 EST TIME: 3.6 minutes Ne rehe(ence O /0 46Co4dh in M e. a n w ee h e A ',n e ,mcJ , -
k+ is nd askJ C in de. quek. %ek -J u nst rc9dred Mr OlI creol;t- .
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COMMONWEALTH EDISON COMPANY QUAD CITIES STATION REQUALIFICATION QUESTION / ANSWER SHEET Point Value: 1.00 Question # 217000 C-1 QUESTION:
Quad Cities Unit I has suffered a small line break loss of coolant accident with the HPCI system out of service. The RCIC system auto initiation occurs at -59 inches RPV level and after some minutes of operation the system trips. When RPV water level again decreases to -59 inches the RCIC system restarts and injects into the vessel.
- a. Assuming no operator action during this transient, what is the most likely cause of the trip of the RCIC system above? (0.5)
- b. State any applicable setpoint(s). (0.5)
ANSWER:
High reactor water level (0.5) ~'
+ 48 inches (0.5)
REFERENCE:
QOP 1300-4, Reactor Core Isolation System Start-up, Rev 8 OBJECTIVE: 8801 MODS AND LESSONS LEARNED Rev. 0 Obj . # 3 TASK XREF: 217-01-01-005, Monitor RCIC operation.
K/A XREF: 217000 A2-01 3.8/3.7 A2.02 3.8/3.7 ,
EST TIME: 2.0 minutes l i
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- COMMONWEALTH EDISON COMFANY lQUAD CITIES STATION l
.REQUALIFICATION QUESTION / ANSWER SHEET 1,
- Point Value: ' l~ 95 -Question #=241000 S-1 QUESTION.:
I
!; With the plant operating with the following conditions:
b .
Reactor Power 98% Core Flow. '98 M1bm/hr
- Steam Flow 9.7 M1bm/hr Feed Flow 9.6~M1bm/hr
' RPV Level 30" Reactor Pressure 1003 psig While reviewing the control panels the NSO observes that reactor pressure has increased about 11 to 12 psig, power has increased and has caused a rod block. and generator output has increas'ed. . The NSO also observes that the "B". pressure regulator is in service, and the light indicating the "A" is coming in and out.
Describe. the' specific steps that must be taken to ensure that the failing regulator does not retake control. (1.95)
ANSWER:
At the 90x-31, find the potentiometer marked pressure setpoint bias
. (0.975), and turn the potentiometer in the clockwise direction, at a moderate rate, until the "A" light goes out and the "B" light is solidly on (0.975).
REFERENCE:
QOA 5650-1, Malfunction of the Pressure Cc: : . el System rev.3 QOP 5650-2,.EHC Pressure Regulator Transfer rev 1 OBJECTIVE:
TASK XREF: 249-01-01-003, Monitor the reactor / turbine pressure regulating system.
341-03-02-051, Interpret / troubleshoot system operation and operability.
,. K/A XREF: 241000 K4.01 3.8/3.8 SG-1 3.7/3.8 L EST TIME: 3.75 minutes L
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l l l COMMONWEALTH EDISON COMPANY l QUAD CITIES STATION l REQUALIFICATION QUESTION / ANSWER SHEET I l
s Point Value: 2.90 Question # 223002 C-1 l
{
QUESTION. .
Some primary containment isolation valve exercise surveillance specify
]
that valve travel shall be timed using the contactor at the breaker to get the stroke time rather than the light indication.
Explain why a properly functioning control room valve position indication is sometimes not allowed as a method of position indication for full ;
stroke timing motor operated containment isolation valves. (2.90)
ANSWER:
Valve position limit switches sometimes are not placed to actuate at full valve travel. (2.90) .
OR __
Motor operated valves may stroke several seconds after indicating full closed. (2.90) i
REFERENCE:
QOS 1600-3, Rev. 1, Primary Containment Motor Operated Valve Testing, p. 2 OBJECTIVE:
TASK XREF: 223-02-01-009, Perform primary containment isolation valve exercise.
K/A XREF: 223002 A1:01 3.5/3.5 SG-10 3.2/3.4 SG-8 3.7/3.6 SC 13 3.8/3.6 EST TIME: 5.6 minutes
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PART A-2 )
l COMMONWEALTH EDISON COMPAMY
) QUAD CITIES STATION.
, REQUALIFICATION STATIC SIMULATOR SCENARIO 12 I
SCENARIO TITLE: BUS 21 OVERCURRENT TRIP / SINGLE LOOP OPERATION SCENARIO TYPE: Abnormal Status l REVISION /DATE: Rev. 1 3 April, 1989 SCENARIO WRITTEN BY: #
INSTRUCTOR Date SCENARIO VALIDATED d///2(// s /O 4b INSTRUCpR/PROJECTLEADER Date ()
SCENARIO APPROVED: / / Lt I(l M //[a < /
PR0t; RAM NANAGER Date /
SCENARIO
SUMMARY
- This exercise begins with the plant operating at 100%
power. With the crew absent from the control room, a.
trip of the Bus 21 occurs causing a loss of one of the operating RFPs, prevents the auto start of the standby RFP, and trips the "A" Recire MG Set.
The reactor was operating in a normal configuration when the unit 1/2 fuel oil day tank HI/LO alarm annunciated. The operators send an A0 out to the diesel room to check on the alarm. Before the A0 reports back, the Bus 21 trips on overcurrent causing a loss of the "A" RFP and a loss of the "A" recirc MG set.
The instructors will silence and acknowledge all alarms. The simulator will be frozen upon the recovery l of the RPV water level to 0 (zero) inches.
MASTER COPY l The General Electric Company rev.1 3 April, 1989 i
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-* COMMONWEALTH EDISON COMPANY' l
- l QUAD CITIES STATION-.
,- REQUALIFICATION STATIC SIMUIATOR SCENARIO 12-MALFUNCTION LISTING: _
1 Malfunctions: j l
K22' Bus 21 Overcurrent Trip
' Remote Functions None Annunciators B35 Recirc MG A/B Fluid Drive Fire B28 Recire MG A/B Drive Motor High. Temp B53 Diesel 2/3 Day Tank Level Hi/Lo l
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T1,e General Electric Company rev.1~ .3 April, 1989
COMMONWEALTH EDISON COMPANY' :
-QUAD CITIES STATION l REQUALIFICATION STATIC SINULATOR SCENARIO 12 SIMULATOR OPERATIONS
SUMMARY
SHEET I. Simulator Setup: ;
A. ~ Initialize the simulator in Mode 10.
B. Change the simulator conditions as follows: q
- 1. Balance all controllers and meters as applicable.
i
- 2. Place Out-of-Service tags on the following equipment; I
- i. None.
- 3. Set up the digital window indicators:
00 Drywell temperature 01 Reactor pressure 02 RPV level
- 4. Place the FWLC in SINGLE ELEMENT control.
- 5. Remove the 90x-8 C-1 (Unit Aux Xformer 21 Trouble) tile cover and replace it with the G-1 (4kv Bus 21 overcurrent)-
tile cover and place the C-1 tile cover in its place.
l 6. If G-1 does not alarm during the setup of the scenario then-
. place an alarm indication on the tile so that the operators will realize that the alarm is in.
- **** **** **a. DO NOT FAIL TO REPLACE THE TILE COVERS TO THEIR ORIGINAL POSITION AT THE tND OF THIS PORTION OF THE !
EXERCISE!!!!
C. .Take the simulator out of freeze.
- 1. Allow the simulator to reach steady state conditions.
(Allow'the simulator to run for approximately 5 minutes.)
L 2. Set the master flow controller to 92% with the recire pumps in b'alance. Once the flow has stabilized, balance the individual pump controllers. Once balanced, place the individual flow controllers in manual.
The General Electric Company rev.1 3 April, 1989 c
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1 COMMONWEALTH EDlSON' COMPANY QUAD CITIES STATION
, REQUALIFICATION STATIC SIMULATOR SCENARIO 12 l
L Place.the "A" FWRV-in manual, set at 30% open. . Place the
~
E, 3.
- ' Low Flow Controller in automatic, set at 25 inches. Also
. place the "B" FWRV:in automatic.
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, 4. Place the."C"_RFP' standby switch in the Bus:21 position.
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- 5. " Advance'all charts to clean paper.
- 6. . Verify the initial plant conditions are as per the Plant Status Turnover Sheet.
II. Scenario Sequence and' Instructor Actions:
A. Five minutes after conditions are stabilized, insert:
B53L Diesel 2/3 Day Tank Level Hi/Lo B35 Recire MG A/B Fluid Drive Fire
~B28 Recirc MG A/B Drive Motor High Temp K22 Bus 21 Overcurrent Trip.
A05 Unit Aux. Trans. 21 Trouble B. An-instructor will perform the following scram actions after the-scram occurs on low water level.
- 1. Press the scram buttons.
- 2. Place Mode switch to SHUTDOWN.
- 3. .Begin inserting SRMs/IRMs.
4 Silence and acknowledge the alarms as required.
- 5. Shut the Recire "A" loop discharge valve.
- 6. Close the "A" FWRV immediately when level. starts to increase.
C. When reactor vessel water level returns to O (zero) inches, freeze the simulator.
III. Post Scenario Actions A. Once the simulator has been frozen, verify the following indications: NOTE: Instrument reading changed from initial conditions: ..
Panel 90x-8 Generator is running and connected to the Grid Annunciators: A-1, C-1, E-1, G-4.
The General Electric Company rev.1 3 April, 1989 L___-___--__-_____
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COMMONWEALTH EDISON COMPANY QUAD CITIES STATION
, REQUALIFICATION STATIC SIMULATOR SCENARIO 12 Panel 90x-7 Turbine is running Annunciators: E-16.
Panel 90x-6 RFP "A" tripped, aux oil pump running RFP "B" running, aux oil pumps tripped RFP "C" still in standby Annunciators: G-5, H-1.
Panel 90x-5 Reactor scrammed SRM/IRMs e INSERTING APRMs: DOWNSCALE Core flow - 62.0 M1b/hr Reactor press - > 900 psig Steam flow -
0.0 M1b/hr Feed flow -
5.4 M1b/hr DW pressure - > +0.6 psig Reactor water level decreasing -
0"/0" GEMAC 0"/0" NR YARWAY Annunciators: A-4,6,10,14,15, B-11,13, C-1,3,5,6, D-1,5,10,13,15, E-5,6,7,8,10,13,15, F-1,3,8, G-2,8, H-4.
, Panel 90x-4 Reactor recirc pump "A" tripped Reactor recirc pump "A" discharge valve shut Recirc pump speed: 92%
Group III isolation Reactor water icvel - 30" Torus temperature - 85/90 F Annunciators: A-3,9,10, B-11, C-1,12, E-5,6, F-1, G-4.
Group II isolation Torus level - -2.5" Annunciators: None.
B. Place the following procedures out for the operators:
- 1. QOA 202-4
- 2. QOA 6500-1 .
- 3. Tech Specs 4 Annunciator procedures The General Electric Company rev.1 3 April, 1989 l
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' COMMONWEALTH EDISON COMPANY QUAD CITIES STATION
- x. REQUALIFICATION STATIC SIMULATOR SCENARIO 12 .,
PLANT STATUS TURNOVER- SHEET The ' plant is in a steady state power level'with normal systems operating.
.RCIC is out of service (day two of a seven day LCO) due to required maintenance. All required surveillance are completed. The'90x-8 G-4 has alarmed, and the crew'is presently investigating the cause. Plans for the upcoming shift is to continue with normal operations.
Plant conditions originally exists as follows:
Core flow -
.98 M1b/hr Reactor press - 1003 psig Recirc 4 flow - 47.0 Mlb/hr Recire A temp - 530 F Recire B flow - 47.0 M1b/hr Recire B temp - 525 F Steam flow - 09.6 M1b/hr Reactor level - 31"/31" GEMAC Feed flow - 09.6 Mlb/hr -
'30"/31" NR YARWAY
- 30" WR APRMs IRMs - Withdrawn 1 - 95 4 - 98 2 - 95 5 - 99 SRM - Withdrawn 3 - 93 6 - 97 DW pressure - +0.71 psig Torus level - 0" DW temperature - 133 F Torus tempera'ture - 85/90 F Setup in the digital window indicators:
00 Drywell temperature 01 Reactor pressure 02 RPV level Current Status:-
A transient occurred. The first alarm in was 90x-4 E-5, Recire MG A/B Drive Motor High' Temp. The crew has taken the following actions:
Press the scram buttons.
I Place mode switch to SHUTDOWN.
I Began inserting SRMs/IRMs.
Silence and acknowledge the alarms as required.
Shut the Recire "A" loop discharge valve.
Closed the "A" FWRV.
l The General 21ectric Company rev.1 3 April, 1989
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COMMONWEALTH EDISON COMPANY QUAD CITIES STATION REQUALIFICATION QUESTION / ANSWER FORM 5 EASTER CC'PY l
l STATIC SCENARIO QUESTION / ANSWER TEST ITEM BANK .
STATIC SIMULATOR OUESTIONS SCENARIO st 12 l i
i PREPARED BY: Michael Orta DATE: 28 Anril 1989 j REVIEWED BY: DATE:
The General Electric Company rev.3 28 April 1989 ,
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g-COMMONWEALTH EDISON COMPANY QUAD CITIES STATION
[ . REQUALIFICATION QUESTION / ANSWER FORM Point Value: 5.25 Question # 12- C-1
' QUESTION L C-1. Assume the plant operator reported that the day tank level was low due to an unisolable leak on the day tank. Explain the status of the 1/2 Diesel Generator's operability. (2.0)- List QOS's that are appropriate and the unit (s) that they should be performed on. (3.25)
ANSWER:
C-1. The diesel generator is considered INOP. (2.0) - -
%~
6'QOS's required (underlined) at (.27) pts each and 6 Unit answers at (.27)' pts eae . o , g gQ1 ha .
QOS 1000-S2 Unit
'& Unit 2
, ,. a y y g %gr_ / c0 QOS 1000-S3 -Unit 1 & Unit 2 QOS 1000-S5 Unit 1 & Unit 2 .97 no QOS 1400-S2 Unit 1 & Unit 2 o ctC.1L ,
QOS 1400-S3 Unit 1 & Unit 2 MtA-QOS 6600-S1
. C '") OOd^- (\'b(DG& ) Unit(MN2D,G b% 104W4
REFERENCE:
TECHNICAL SPECIFICATIONS 3.9.A.1, 3'.9.E.1, 4.9.E.1, 4.9.A BASES AMENDMENT 114 QOS 6600-03 , SHARED UNIT (1/2) DIESEL GENERATOR OUTAGE REPORT 7 DAY LIMITATION rev.5 QOS 1000-S2 RHR AND RHR SERVICE WATER PUMP OPERABILITY DATA SHEET rev.5 QOS 1000-S3 LPCI MOTOR OPERATED VALVE OPERABILITY TEST DATA SHEET rev.5 QOS 1000-S5 RHRS CONTAINMENT COOLING DATA SHEET VALVE
/ OPERABILITY rev.6 h,p QOS 1400-S2 QOS 1400-S3 CORE SPRAY MOTOR OPERATED VALVE OPERABILITY DATA SHEET rev.3 CORE SPRAY PUMP OPERABILITY TEST rev.2 QOS 6600-S1 MONTHLY DIESEL GENERATOR AND SYSTEM OPERABILITY TEST DATA SHEET rev.8 OBJECTIVE:
TASK XREF: 299-03-01-015, Apply Technical Specification Requirements.
341-03-02-018, Apply Technical Specifications. directions for safety limits, safety system settings and limiting conditions for operations.
K/A XREF: 264000 K1.05 3.2/3.3 SG-5 3.4/4.1 SG-11 3.4/4.1 -
EST TIME: 5.8 minutes PREPARED BY: Michael Orta DATE: 28 April 1989 REVIEWED BY: DATE:
The General Electric t;ompany rev.3 28 April 1989
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'* - COMMONWEALTH EDISON ~ COMPANY QUAD CITIES STATION :q
, REQUALIFICATION QUESTION / ANSWER FORM
- 1. l l.
Point Value: 4 . 5_ Question # 12--C-2
- QUESTION C-2. Explain why the total core flow!indication is inaccurate during single. loop operations. (4.5)
ANSWER:
C-2. Because of the reverse flow going through the jet pumps of the idle loop. (4.5) q
REFERENCE:
QOA 202-4, LOSS OF FLOW'- SINGLE PUMP rev.8 QOS 202-11, CALCULATION OF TOTAL REACTOR CORE FLOW DURING ONE RECIRCULATION PUMP OPERATION rev.4 OBJECTIVE:
' TASK XR".F: .202-01-01-007, Monitor jet pump operation.
341-03-02-051, Interpret / troubleshoot system operation and operability.
344-03-02-001,' Analyze indications to determine that an abnormal plant event.is'in progress.
K/A XREF: 202001 .A4.04 3.7/3.7 A4.12 3.9/3.9 EST TIME: 4.0 minutes e
PREPARED BY: Michael Orta DATE: 28 April 1989 REVIEWED BY: DATE:
The. General Electric Company rev.3 28 April 1989
, ,*. s COMMONWEALTH EDISON COMPANY QUAD CITIES STATION
.PIQUALIFICATION QUESTION / ANSWER FORM Point Value: 2.25 Question # 12- C-4 QUESTION C-4 Why didn't the "C" RFP start automatically. (2.25) i i
i ANSWER:
C-4. The "C" RFP is selected to the Bus 11(21), which was lost. j I
'l.25)
(2 2$
REFERENCE:
Control Room Indications, 90x-6 panel RFP Standby Selector Switch OBJECTIVE:
TASK XREF: 259-01-01-004, Monitor the operation of a reactor feedwater i pump.
341-03-02-051, Interpret / troubleshoot system operation and operability.
K/A XREF: 259001 K4.01 3.8/4.0 A2.06 3.2/3.2 EST TIME: 1.6 minutes
}ypo CorNCNY 1
PREPARED BY: Michael Orta DATE: 28 April 1989 REVIEWED BY: DATE:
The General Electric Company rev.3 28 April 1989
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COMM0i? WEALTH EDISON' COMPANY QUAD CITIES STATION
, REQUALIFICATION QUESTION / ANSWER FORM Point Value: 2.25 Question # 12- C-5 QUESTION C-5. What caused the loss of Bus 217 (2.25)
I ANSWER:
C-5. The bus tripped on a bus overcurrent condition. (2.25)
- Possible answer to be accepted,**
The Bus tripped due to the recirculation MG set problem. (2.25)
REFERENCE:
Control Room Indication, 90x-8 F-3 4kv Bus Overcurrent OBJECTIVE:
TASK XREF: 299-03-01-009, Report abnormal parameters or conditions.
344-03-02-006 Analyze indications to determine the cause of the abnormal or emergency event K/A XREF: 262001 A3.01 3.1/3.2 SG-8 3.5/3.4 EST TIME: 1.6 minutes PREPARED IW: Michael Orta DATE: 28 April 1989 REVIEWED BY: DATE: !
The General Electric Company rev.3 28 April 1989 l
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'N.-QUAD CITIES STATION c , !REQUALIFICATION QUESTION / ANSWER FORM m -
, :PointLValue: 2.25 Question # 12- C-6 QUESTION '
.iC-6. What' caused'the automatic reactor scram? (2.25)
.. ANSWER:
C-6. ILow reactor water Icvel (+8 inches). .(2.25)
REFERENCE:
Contirol Room Indications, . 90x-5 panel first up . .
annunciators, RPV level recorders.
OBJECTIVE:
TASK.XREF: (200-05-01-031, Rezognize and respond to a reactor water level low.
'344-03'-02-006' Analyze' indications to determine the cause of the abnormal or emergency event K/A XREF: .295009 SG-5 3.7/3.6 SG-11 4.3/4.5
'.: EST TIME: 1.6 minutes l
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PREPARED BY: ' Michael Orta DATE: 28 April 1989 REVIEWED BY: DATE:
The General Electric Company rev.3 28 April 1989 I-m____. ___n__.._____. _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _. _ _ _ _ . _ _ _ _ _ _ . . _ _ _ _ . _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
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COMMONWEALTH EDISON COMPANY QUAD CITIES STATION a
REQUALIFICATION QUESTION / ANSWER FORM Point Value: 5.25 Question # 12- C-7 QUESTION C-7. Based on panel indications describe the present mode of feedwater level control. Include in your' answer events that initiated that mode. (5.25)
ANSWER:
C-7. The feedwater level control system has gone into the runout flow control mode of operation (2.625). This is because the feedwater pump exceeded its runout flow limit [5.6 M1bm/hr)
(2.625) causing the feedwater system to go into the flow control mode.
REFERENCE:
Control Room Indications, 90x-8, Bus.21 Overcurrent, 90x-6, RFP trip, 90x-5, Feedwater flow recorder, APRMs, Steam flow recorder, RPV water level.
QOA 90x-5 G-8 FEEDWATER PUMP MAX CAPACITY rev.4 OBJECTIVE:
TASK XREF: 299-03-01-009, Report abnormal parameters or conditions.
344-03-02-006 Analyze indications to determine the cause of the abnormal or emergency event K/A XREF: 259001 K6.03 2.9/3.1 A2.01 3.7/3.7 EST TIME: 5,6 minutes i
1 Michael Orta DATE: 28 April 1989 PREPARED BY:
REVIEWED BY: DATE:
The General Electric Company rev.3 28 April 1989 l I
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COMMONWEALTH EDISON-COMPANY QUAD CITIES STATION
. REQUALIFICATION QUESTION / ANSWER FORM Point Val'ue: 2.00 Question # 12 -C-8 F
l QUESTION'-
1 .
C-8. Why are the. Reactor Water Cleanup valves; MO 1201-21, M0 1201-5, and MO 1201-80 valves are-closed? Include in your answer
-applicable settioint(s). (2.00)
ANSWER:
'C-8, Group III isolation (1.0),-
at +8". reactor vessel water. level (1.0) s
REFERENCE:
QGA 100-1 RPV Level Control rev.3
' REACTOR WATER CLEAN-UP SYSTEM'- SHUTDOWN, QOP 1200-8 Limitations and Actions, E.2.a6 rev.2 OBJECTIVE:
TASK XREF: .299-03-01-009, Report abnormal parameters or condition.
344-03-02-001,' Analyze indications to determine that an abnormal plant event is in progress.
K/A XREF: 204000 K4'.04 3.5/3.6 EST TIME: 1.4 minutes 4
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Michael Orta DATE: 28 April '1989 PREPARED BY:
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'- REVIEWED BY: DATE:
The General Electric Company rev.3 28 April 1989
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l COMMONWEALTH EDISON COMPANY l QUAD CITIES STATION REQUALIFICATION QUESTION / ANSWER FORM Point Value: 3.5 Question # 12- C-9 QUESTION C-9. QGP 2-3 states that the recirculation pumps should have runback.
Given the present plant conditions why didn't the "B" reactor recirculation pump runback? Include any applicable setpoint(s).
(3.5)
ANSUER:
(ROVb 6
C-9. Feedwater flow (1.75), greater than 2 x 10 lbm/hr." (1.75)
REFERENCE:
QGP 2-3 REACTOR SCRAM rev.26 step D.8 OBJECTIVE:
TASK XREF: 299-03-01-009, Report abnormal parameters or conditions.
344-03-02-009, Evaluate abnormal event to determine that conditions are following expected sequence (e.g., proper instrumentation response).
K/A XREF: 202001 K4.16 3.3/3.6 EST TIME: 2.8 minutes Q g g h he'sft] b$ Y in WC" N d accepM6 b N8b PREPARED BY: Michael Orta DATE: 28 April 1989 REVIEWED BY: DATE:
The General Electric Company rev.3 28 April 1989 l
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COMMONVEALT11 EDISON COMPANY l QUAD CITIES STATION l
. REQUALIFICATION QUESTION / ANSWER FORM l Point Value: 3.00 Question # 12- C-10 ,
QUESTION C-10. Briefly state why the two wide range yarway (2-263-106 A & B) indications don't coincide? (3.0)
ANSWER:
C-10. Because the "B" recire pump is still operating and the "A" pump is shutdown. (3.0)
REFERENCE:
QGA Caution #8 rev.8 OBJECTIVE- l TASK XREF: 299-03-01-009, Report abnormal parameters or conditions.
344-03-02-009, Evaluate abnormal event to determine that conditions are following expected sequence (e.g., proper instrumentation response).
K/A XREF: 216000 A2.09 3.1/3.2 EST TIME: 2.4 minutes l
PREPARED BY: Michael Orta DATE: 28 April 1989 REVIEWED BY: DATE:
The General Electric Company rev.3 28 April 1989
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l COMM0!! WEALTH EDISON COMPANY- ]
. QUAD CITIES STATION j
. REQUALIFICATION QUESTION / ANSWER FORM Point Value: 5.25 Question # 12- C-20
'l l QUESTION C-20. NOT SPECIFICALLY RELATED TO THE SCENARIO:
~
. Assume that the reactor did-not scram and the'"A" recire pump is tripped.- The following is.a list of parameters concerning the-plant operation:
Prior to the recire pumo trin 6
Core Flow.... 98 x10 lbm/hr Rx Pwr....... 100%
After the'recire Dumo trin 6
Core flow.... 49 x10 lbm/hr (calculated per QOS 202-11)
Determine the FCL (flow contr,1 line) that existed prior to the pump trip (2 625) and the reector power after the pump trip
.(2.625).
ANSWER:
C-20.: The 100% flow control line (2.625), and 64% (+/- 2%) reactor power (2.625)
REFERENCE:
QOS 202-12, DETERMINATION OF FLOW CONTROL LINE FROM THE POWER / FLOW MAP rev.1 pp.1,2 QoS 202-T16 TYPICAL POWER / FLOW MAP rev.1 OBJECTIVE:
l TASK XREF: 200-04-01-001, Recognize and respond.to a single recirculation pump trip.
202-01-01-006, Monitor the recirculation pumps in operation.
202-01-02-006, Monitor the recirculation pumps in operation.
K/A XREF: 202002 SG-10 3.3/3.3 SG-12 3.6/3.4 295001 AA2.01 3.5/3.8 EST TIME: 5.1 minutes .
PREPARED BY: Michael Orta DATE: 28 April 1989 +
REVIEWED BY: DATE:
The General Electric Company rev.3 28 April 1989
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, .' . COMMONWEALTH EDISON COMPANY.
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QUAD CITIES STATION -
P 'REQUALIFICATION QUESTION / ANSWER FORM
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' Point Value: 2.00 Question # 12 - C-21
. QUESTION CA21. 'NOT'SPECIFICALLY RELATED TO THE SCENARIO:
L If during extended. single loop operation' core plate d/p noise;
. exceeds l' psi. peak-to-peak, what operator action (s) is required .
to be performed with the reactor recirculation system?- (2.00)
~
ANSWER:'
ic C-21. -Reduce the operating pump speed. '(2.00)'
I
REFERENCE:
QOA-202-4, LOSS'0F FLOW . SINGLE PUMP rev.8 step D.2.e i
1 OBJECTIVE:
TASK XREF: 200-04-01-001, Recognize and respond to a single recirculation pump trip.
341-03-02-051,- Interpret / troubleshoot system operation and operability.
K/A XREF: 202002 SG-1 3.6/3.7 SG-10 3.3/3.3 :
EST TIME: 1.5 minutes l
, I
' PREPARED BY: Michael Orta DATE: 28 Anril 1989 REVIEWED BY: DATE:
The GeneraliElectric Company rev.3 28 April 1989 h
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COMMONWEALTH EDISON COMPANY QUAD CITIES STATION REQUALIFICATION QUESTION /ANSVER FORM Point Value: 3.00 Question # 12 - S-1 QUESTION b-1. NOT SPECIFICALLY RELATED TO THE SCENARIO:
Explain why the rods are inserted to reduce power below 40%, if the total core flow is determined to be less than 45 M1bm/hr, per QOA 202-4, step C.4. (3.0)
ANSWER:
S-1. To prevent operation in the area of the power flow map where continuous operation is not permitted (the area where power oscillations have been experienced.) (3.0)
OR Because control rod insertion is more conservative than a -
non-safety related action such as a recirculation pump restart.
(3.0)
REFERENCE:
QOA 400-2, CORE INSTABILITIES rev.2 l QOA 202-4, LOSS OF FLOW - SINGLE PUMP rev.9 QOS 202-T16, TYPICAL POWER - FLOW MAP rev.1 OBJECTIVE:
TASK XREF: 344-03 02-004, Evaluate the adequacy of abnormal and emergency procedures for mitigation capabilities during abnormal conditions.
K/A XREF: 295001 AK1.04 2.5/3.3 EST TIME: 2.4 minutes 1
l PREPARED BY: Michpel Orta _ DATE: 28 Anril 1989 I
REVIEWED BY: __ DATE: '
The General Electric Company rev.3 28 April 1989 l
l
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, COMMONWEALTH EDISON COMPA!U QUAD CITIES STATION REQUALIFICATION QUESTION / ANSWER FORM
? .
Point Value: 5.00 Question # 12- S-2 QUESTION S-2. Explain why the MCPR Safety Limit and MCPR operating limit are increased for single loop operation. (5.0)
ANSWER:
S-2. The MCPR Safety limit has been increased (by 0.01) to account for core ficw and TIP reading uncertainties, (2.5) also to maintain the same amount of margin to the safety limit as during duel loop operations. (2.5)
REFERENCE:
TECHNICAL SPECIFICATIONS 3.6 Bases section H AMENDMENT 114 QOA 202 4,. LOSS OF FLOW - SINGLE PUMP, rev.8 pp.1-3 OBJECTIVE:
TASK XREF: 341-03-02-018, Apply Technical Specifications ' directions for safety limits, safety system settings and limiting conditions for operations.
K/A XREF: 202001 SG-10 3.5/3.7 EST TIME: 4.3 minutes PREPARED BY: Michael Orta DATE: 28 April 1989 REVIEWED BY: _ DATE:
The General Electric Company rev.3 28 April 1989 I
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COMMONWEALTH EDISON COMPANY QUAD CITIES STATION
- REQUALIFICATION QUESTION / ANSWER FORM Point Value: 4.25 Question # 12- S-3
. QUESTION S-3. If a 1/2 Diesel Generator is declared inoperable, explain whether or not the ECCS systems, feed from the 1/2 Diesel Generator, are operable under the present plant conditions. (4.25)
ANSWER:
S-3. 1. Its corresponding normal power source is operable, (4.25)
(All of its redundant systems, subsystems, trains, components, and devices in the other division are OPERABLE, ,
or likewise satisfy the requirements of this specification.)
REFERENCE:
Technical Specifications 3.0.B Amendment #72 p. 3.0/4.0 2 OBJECTIVE:
TASK XREF: 299-03-01-015, Apply Technical Specification Requirements.
341-03-02-018, Apply Technical Specifications directions for safety limits, safety system settings and limiting. conditions for operations.
K/A XREF: 264000 SG-11 3.4/4.1 .
EST TIME: 3.6 minutes PREPARED BY: Michael Orta DATE: 28 Anril 1989 REVIEWED BY: DATE:
The General Electric Company rev.3 28 April 1989
PART A-1 -
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COMMONWEALTH EDISON COMPANY QUAD CITIES STATION' REQUALIFICATION STATIC SIMULATOR SCENARIO 7 SCENARIO TITLE:
TURBINE TRIP AT S MASTEli COP SCENhRIO TYPE: Major Failure j REVISION /DATE: Rev. 1 3 April, 1989 1
SCENARIO WRITTEN BY: /N #
INSTRUCTOR Date SCENARIO VALIDATED: d2A A4/ // h 824' iNSTgCTOR/P'ROJECTLEIADER Date ()
SCENARIO APPROVED: / / A fl M < / If
/P ROGPM MANAGER Dat'e/
SCENARIO
SUMMARY
- This exercise begins with the plant operating at 40 to 45% power. With the crew absent from the control room, a turbine trip occurs with a failure of the control rods to insert.
The reactor is operating in a normal configuration when the turbine trip occurs. The feedwater temperature ;
decreases causing reactor power to increase to the i scram setpoint. The scram signals result in the scram valves opening, however the control rod blades do not insert. The operators should be concerned with the shutdown of the reactor and any possible containment issues.
-The instructors will perform the actions through step 4 for a reactor scram per QGP 2-3. The simulator will be frozen when the scenario has run for 40 seconds and reactor pressure has decreased back to the scram l setpoint.
The General Electric Company rev.1 3 April, 1989 FEASTER COP'
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s COMMONWEALTH EDISON COMPANY QUAD CITIES STATION REQUALIFICATION STATIC SIMULATOR SCENARIO 7 MALFUNCTION LISTINGe Malfunctions:
C42 Failure of CRD Hydraulic to Insert Annunc. A23 Turb. Trip Thrust Bearing Failure J22 Turbine Trip Remote Functions:
None Annunciators:
None The General Electric Company .rev.1 3 April, 1989
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COMMONWEALTH EDISON COMPANY.
QUAD CITIES STATION'
"- REQUALIFICATION STATIC SINULATOR SCENARIO 7 SIMULATOR OPERATIONS SPMMARY SHEET I. Simulator Setup:
A. Initialize the simulator in Mode 10.
B. Change the simulator conditions as follows:
- 1. Set the simulator up for Quad Cities Station.
- 2. Set the master flow controller to minimum with the recire pumps in balance.
- 3. Balance all controllers and meters as applicable.
- 4. Place Out-of-Service tags on the following equipment;
'l
- 5. Set up the digital window indicators:
l i
00 Drywell temperature 01 Reactor pressure ]I 02 RPV level ~j
- 6. Place the FWLC in SINGLE ELEMENT control.
l C. Take the' simulator out of freeze. !
- 1. Allow-the simulator to reach steady state conditions. {
- 2. Bal'ance the individual pump controllers. Once balanced, place the individual flow controllers in manual.
- 3. Place the "A" FWRV in manual, closed. Place the Low Flow controller in automatic, set at 25 inches. Also place the l "B" FWRV in automatic.
- 4. Verify the initial plant conditions are as per the Plant Status Turnover Sheet.
The Ceneral Electric Company rev.1 3 April, 1989 l
i
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COMMONWEALTH EDISON COMPANY in QUAD CITIES. STATION
' *" 'REQUALIFICATION STATIC SINULATOR SCENARIO 7
'l II. Scenario Sequence and Instructor Actions:
' A ~.
Five minutes after conditions are stabilized, advance all charts to clean paper, then insert:
L C42 Failure of CRD Hydraulic to Insert Annunc. A23 Turb. Trip - Thrust Bearing Failure J22 Turbine Trip B. .An instructor will perform the following actions during the scenario.
- 1. Press the scram buttons, when reactor pressure reaches 1050 psig.
- 2. Place Mode switch to SHUTDOWN.
- 3. Insert IRMs/SRMs, (plant / simulator difference).
- 4. . Trip the recire when the relief valves first open.
C. When the scenario has run for.40 seconds and reactor pressure has decreased below the scram setpoint (1060 psig),'and the recire pumps tripped, freeze the simulator.
- 1. Take a snapshot, so that scenario is not lost in the event of the sleep routine.
III. Post Scenario Actions A. Once the simulator has been frozen, verify the following.
indications: NOTE: Instrument read.ing changed from initial conditions:
Panel 90x-8 Generator has tripped Aux power has transferred Annunciators: A-1,12, B-1,5,12, C-5, D-1, F-12.
Panel 90x-7 Turbine has tripped Turbine stop and control valves are closed All turbine bypass valves open Stator water cooling pumps tripped, j .-
Annunciators: A-5, B-10, C-3,10, E-16, G-3.
s.
Panel 90x-6 RFP recire valves open Annunciators: G-5,9, H-1.
The General Electric Company rev.1 3 April, 1989
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L,
. COMMONWEALTH EDISON CDMPANY
- ,, tQUAD CITIES STATION
- - REQUALIFICATION STATIC SINULATOR SCENARIO 7
. Panel 90x-5 Reactor scrammed, mode switch in shutdown Blue scram lights lit APRM and IRM Hi-Hi alarm lights lit.
Rods not in SRM/IRMs - INSERTING ^ APRMs: approx. 35'to 40%
Core flow - 30.0 M1b/hr- Reactor press - < 1060 psig
' Steam flow - 4.0 M1b/hr Feed flow - 0.0 - 2.0 M1b/hr DW pressure +0.70 psig Reactor water level decreasing .- 15"/15" GEMAC ~ ) 4" 13"/13" NR YARWAY ) 4" Annunciators: A-4,5,6,10,12,14,15, B-11, C-1,3,10,12,13,15, D-1,10,13,15, E-6, F-1,3,8, G-2, H-4,5.
Panel 90x-4 Recire pump speed: tripped Reactor water level - 40" WR Torus temperature - 85/90 F Annunciators: A-3,7, H-17,19.
Torus level - 0" '
Annunciators: C-13, D-13.
B. Place the following procedures out for the operators:
- 1. QGP 2-3, open to step 4
- 2. QGA 100-1 The General Electric Company rev.1 3 April, 1989
COMMONWEALTH EDISCN COMPANY QUAD CITIES STATION REQUALIFICATION STATIC SIMULATOR SCENARIO 7 PIANT STATUS TURNOVER SHEET The plant is at a steady state power level of 50% with normal systems operating. RCIC is out of service (day two'of a seven day LCO) due to required maintenance. All required surveillance are completed. The.B2 recirc MG set AC oil pump is also out-of-service. Plans for the upcoming shift is to continue with normal operations.
Plant conditions originally exist as follows:
Core flow - 40.0 Mlb/hr Reactor press - 948 psig Steam flow - 04.1 M1b/hr Reactor level -
31"/31" GEMAC Feed flow - 04.0 Mlb/hr -
30"/30" NR YARWAY Recire pump speed: minimum - 30" WR s
APRMs IRMs - Withdrawn 1 - 43 4 - 44 2 - 43 5 - 41 SRM - Withdrawn 3 - 40 6 - 43 DW pressure - +0.29 psig Torus level - 0" DW temperature - 129 F Torus temperature - 85/90 F Setup in the digital window indicators:
00 Drywell temperature 01 Reactor pressure 02 RPV level Current Status:
A transient occurred. The first alarm in was 90x-7, A-5 and 90x-5, A-12. Turb Bypass Valve Open and Channel A/B Stop Vis Cisd > 40%
Load. The crew has taken the following actions:
Pressed the scram buttons, Place Mode switch to SHUTDOWN.
Tripped the recire pumps.
Silenced and acknowledged the alarms.
The General Electric Company rev.1 3 April, 1989
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e COMMONWEALTH EDISON COMPANY QUAD CITIES STATION REQUALIFICATION QUESTION / ANSWER FORM FEASTER COoY STATIC SCENARIO QUESTION / ANSWER TEST ITEM BANK i
STATIC SIMULATOR OUESTIONS SCENARIO # 2 DATE: 28 Anril 1989 PREPARED BY: Michael Orta REVIEWED BY DATE:
The General Electric Company rev.2 28 April, 1989
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COMMONWEALTH EDISON COMPANY QUAD CITIES STATION REQUALIFICATION QUESTION / ANSWER FOPE Point Value: 5.25 Question # 7 - C-1 QUESTION C-1. With the current drive header pressure indications, state what action (s) must be taken, with regards to the CRD Hydraulic System, to insert control rods. (5.25)
ANSVER:
C 1. The CRD-25 valve must be shut. (5.25)
REFERENCE:
QGA 100-3, RPV Power Control step L-1, rev.2 OBJECTIVE:
TASK XREF: 200-05-01-020, Failure of reactor to scram when required or l failure of control rods to fully insert during scram.
344-03-02-007, Direct corrective action to mitigate the consequences of the abnormal event.
K/A XREF: 201001 A1.01 3.1/2.9 A2.04 3.8/3.9 295037 EK3.07 4.2/4.3 l EST TIME: 5.25 minutes l
l DATE: 28 April 1989 PREPARED BY: Michael Orta l REVIEWED BY DATE:
The General Electric Company rev.2 28 April, 1989 !
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' COMMONWEALTH EDISON COMPANY-
. QUAD. CITIES STATION
+ ~REQUALIFICATION QUESTION / ANSWER FORM Point Value: 4.75 Question # 7 - C-4 QUESTION C-2. In the present plant conditions, list three (3) scram signals that are preventing the reactor scram from being reset. (4.75)
ANSWER:
i C-2. At (0.1.59)ptsgg,
- 1. APRMsabove155(withmodeswitchinSHUTD0h
- 2. IRM High-High.
- 3. SDV High-High level 7pv9 % u > ID(oO '(&d wh > IOd cLpc3 \05'7 ,
REFERENCE:
Control Room Indications, 90x-5 "B" Panel. alarms 0BJECTIVE:
200-04-01-033, Recognize and respond to a reactor scram.
TASK XREF:
344-03-02-006 Analyze indications to' determine the cause of the abnormal or emergency event-K/A XREF: 295006 SG-5' 4.1/4.0 SG-7 3.8/4.1 EST TIME: 4.1 minutes Qstp.;,& mt speciOGlly asked.0 u if *a nd rt9dere0*
'fM dedlhA is dh A *S C#'k1 N fWe so#
,5- w ey a;,eJ
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DATE: 28 Acril 1989 PREPARED BY: Michael Orta REVIEWED BY DATE:
The General Electric Company rev.2 28 April, 1989 i
l
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COMMONWEALTH EDISON COMPANY QUAD CITIES STATION REQUALIFICATION QUESTION / ANSWER FORM Point Value: 3.5 Question # 7 - C-5 QUESTION C-5. What systems are available for contro11in6 reactor pressure?
Assume that all systems that are operating are operating correctly. (6 required for full credit) (3.5)
ANSWER:
C-5. HPCI (0.59)
ADS valves (0.59)
Turbine Bypass Valves (0.59)
SJAE (0.59)
MSL drains (0.59)
RUCU-(Recire or Blowdown) (0.59) 0 rev.2 J A9
REFERENCE:
QGA 100-2 RPV Pressure Control step E-4 and H-3 -
9pt OBJECTIVE:
TASK XREF: 200-05-01-020, Failure of reactor to scram when required or [~ '
failure of control rods to fully insert v during scram. .
344-03-02-024, Direct corrective actions to' mitigate the consequences of the emergency event.
L[5 g
L, K/A XREF: 295037 SG-12 3.9/4.6 g ,
2.9 minutes &
EST TIME:
I i
1 I
i i
DATE: 28 April 1989 j PREPARED BY: Michael Orta REVIEWED BY DATE:
The General Electric Company rev.2 28 April, 1989
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. .. i COM.10NWEALTH EDISON COMPANY QUAD CITIES STATION
- REQUALIFICATION QUESTION /ANSWOR FORM I'oint Value: 3.00 Question # 7 - C-8 i
j QUESTION C-8. With the present plant conditions, adequate core cooling is being maintained by core submergence. If RPV water level indication is lost, state a method that will be used to assure adequate core cooling? (3.0)
ANSWER:
C-8. Either required for full credit. (3.0)
Adequate Core Cooling is maintained by:
Steam cooling OR Maintaining pressure above mar?.
REFERENCE:
QGA 500-7g2, Level / Power Control (Flooding)
OBJECTIVE:
TASK XREF: 200-05-01-020, Failure of reactor to scram when required or failure of control rods to fully insert during scram.
344-03-02-028, Direct actions to ensure that core cooling and the subcooling margin are maintained
- during an emergency event.
K/A XREF: 295037 EA2.02 4.1/4.2 SG-11 4.4/4.7 SG-12 3.9/4.6 EST TIME: 2.25 minutes i DATE: 28 April 1989 PREPARED BY: Michael Orta DATE:
REVIEWED BY The General Electric Company rev.2 28 April, 1989
- _ _ - - _ - _ . -^--%-- - - - - _ . - _ _ , _ _ _ _ _
COMMONWEALTH EDISON COMPANY QUAD CITIES-STATION REQUALIFICATION QUESTION / ANSWER FORM ~ i Point Value: 3.00 Question # 7 - C-9
. QUESTION C-9. A positive reactivity addition occurred due to the increase in reactor pressure. State another plant condition,.that has-
! occurred, that will continue to add positive reactivity as the transient progresses. (3.25)
ANSWER:
C-9. The loss of feedwater heating (due to the turbine trip). (3.25)
REFERFNCE: QOA 400-1 REACTIVITY ADDITION D.6.f rev.4-QOA 3500-1 1 DSS OF FEEDWATER HEATERS rev.4 i
OBJECTIVE:
TASK XREF:- 200-05-01-020, Failure of reactor to scram when required or i failure of control rods to fully insert during scram.
344-03-02-001, Analyze indications to determine that an
-abnormal plant event is in progress.
K/A XREF: 295037 EK1.06 4.0/4.2 SG-7 3.7/3.9 EST TIME: 2.6 minutes l
l DATE: 28 April 1989 i PREPARED BY: Michael Orta REVIEWED BY DATE: .
28 April, 1989 j The General Electric Company rev.2 1
1
1
> COMMONWEALTH EDISON COMPANY QUAD CITIES STATION
, REQUALIFICATION QUESTION / ANSWER FORM Point Value: 2.25 Question # 7 - C-11 QUESTION C-11. How would the operator restart the Stator Water Cooling pump?
(2.25) i ANSWER:
C-11. Having the generator-86 device reset will restart the Stator Water Cooling purap. (2.25)
REFERENCE:
QGP 2-3 REACTOR SCRAM D.10.b rev.26 OBJECTIVE:
TASK XREF: 253-01-01-002, Startup thre Stator Water Cooling System.
341-03-02-051 Interpret / troubleshoot systep operation and operability.
K/A XREF: 245000 SG-1 3.3/3.5 SG-13 3.2/3.2 EST TIME: 1.6 minutes DATE: 28 April 1989 PREPARED BY: Michae'i Orta REVIEVED BY DATE:
The General Electric Company rev.2 28 April, 1989
e COMMONWEALTH EDISON COMPANY QUAD CITIES STATION PJ. QUALIFICATION QUESTION / ANSWER FORM Point Value: 2.00 Question # 7 - C-12 QUESTION 0-12. What signal should have caused the Reactor Protection System to have tripped. (2.00)
ANSWER:
C-12. StopValvesclosed(greaterthan40% Load)(2.00)
REFERENCE:
Control Room Indication, QOA 90x-5 A-12 CHANNEL A/B STOP VLVS CLOSE TRIP rev.20 OBJECTIVE:
TASK XREF: 212-01-01-005, Monitor the reactor protection system.
344-03-02-006 Analyze indications to determine the cause of the abnormal or emergency event K/A XREF: 295006 AA2.06 3.5/3.8 EST TIME: 1.5 minutes Ne $19 Vdc Chwe u ne %e af de scraan, dids, >4'D%, h fred $$ by ks -
the. $Nnf h psf requirtY h N SY L/sdic Le,$4 & bWe
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1 DATE: 28 April 1989 i PREPARED BY: Michael Orta )
REVIEWED BY DATE:
The General Electric Company rev.2 28 April, 1989 l l
1 4
'f? ..- 00A'900-5-A Revision 20 ALARM DETECTS /
.<IP TION- AUTO ACTION IMMEDIATE OPERATOR ACTION
$NNEL A. .
- 1. Manual scram. 1. Verify Rx parameters normal.
iANUAL SCRAM 2. Loss of RPS Bus A 2. RESET the half scram.
power. 3. If due to loss of power refer to QOP 7000-1.
- 4. Notify the Shift Engineer.
- 5. If " white" scram group lights 1, 2, 3, 4 are lit, check faulty alarm circuit.
- 6. If due.to circuit failure check the MANUAL SCRAM pushbutton light.
- a. If not lit, check relays 109A and 109C.
- b. 'If lit, check faulty connec-tions at mode switch or at shutdown reset interlocks.
- 1. Condenser vacuum 1. If in RUN refer to SCRAM pr0tedure A-II. CHANNEL A/B (67) CONDENSER LO < 21 in. Hg Vac. QGP 2-3. .
VACU 21 IN HG monitored by 2. Verify SJAE and CIRC water pumps:
channel A are operating normally. ,
and/or B 3. Notify the Shift Engineer. l
- 4. If VAC cannot be recovered, shut-(' down to Hot Standby in accordance with QGP 2-4. t
- 5. If Cond VAC ),21 inches Hg., check (
circuitry. j ll 1
A-12 CHANNEL A/B ,: 1. Closure of at 1. If 1.40% load, refer to scram (68) STOP VLVS CLOSE least two turbine procedure QGP 2-3.
l TRIP stop valves. 2. If turbine did not trip, check for closure of 2 MSVs. Verify turbine BPVs are controlling press.
- 3. Notify Shift Engineer and Load l Dispatcher. '
i
- 4. Reduce power until BPVs are closed.
- 5. Do not test another MSV. !
- 6. Closure of one MSV will not give l alarm. ,,
1 i APPROVED l 2/0026o JAN 191939 c.c.o.s.a. l
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e COMMONWEALTH EDISON COMPANY QUAD CITIES STATION REQUALIFICATION QUESTION / ANSWER FORM Point Value: 3 . 7 5 -_ Question'# 7 - C-14 QUESTION C-14 List three (3) front panel indications that indicate to the j operator that the B and C ADS valves ace OPEN. (3.75) fun, N ANSWER:
C-14, 3 out of 4 required for f. , credit at (1.25) pts each.
- 1. B and C valve position indication (10 Nd #ms Mg omkligh
- 2. Acoustic Monitor alarm
- 3. Valve Leak Detector Sys High Temp Alarm
- 4. Valve open alarms
REFERENCE:
QOS 201-1 MANUAL OPERATION OF ELECTROMATIC RELIEF VALVES rev.11, step F.7,8 QOA 90x-3 D-13 ELECT RELIEF VALVE 3A, 3B OPEN rev.10 QOA 90x-3 E-13 ELECT RELIEF VALVES 3C/3D/3E OPEN rev.11 QOA 90x-3 E-14 ACOUSTIC MON SAFETY-RELIEF VALVES OPEN tev.11 QOA 90x-4 H-17 VALVE LEAK DETECTOR SYS HICH TEMP rev.11 OBJECTIVE:
TASK XREF: 200-05-01-018, Recognize and respond to a reactor high pressure.
344-03 02-004, Evaluate the adequacy of abnormal and.
emergency procedures for mitigation capabilities during abnormal conditions.
K/A XREF: 295007 SG-12 3.7/4.4 EST TIME: 3.1 minutes Que6NA W 8 N "
)$ lhe Onts0U bly Chis ICahEm i
I PREPARED BY: Michael Orta DATE: 28 Avril 1989 l REVIEWED BY DATE:
f rev.2 28 April, 1989 l
The General Electric Company i
=
J COMMONWEALTH EDISON COMPANY t
QUAD CITIES STATION
. REQUALIFICATION QUESTION / ANSWER FORM Point Value: h Question # 7 - C-15 !
QUESTION C-15. Assuming you are able to drive. control rods, which rod will you start with (1.75), and what method would you use'to select the next for insertion? (1.75) t ANSWER:
'C-15. Central rod (1.75) and spiraling out from the center. (1.75) i
REFERENCE:
QOA 300-15 MANUAL CONTROL ROD INSERTION FOLIDWING AN ;
ATWS EVENT rev.1 OBJECTIVE:
TASK XREF: 200 05-01-020, Failure of reactor to scram when required or failure of control rods to fully insert during scram.
344-03-02-024, Direct corrective action to mitigate the consequences of the emergency event.
K/A XREF: 295037 -SG-12 3.9/4.6 -
2ST TIME: 3.0 minutes A
PREPARED BY: Michael Orta DATE: 28 Acril 1989 REVIEWED BY DATE:
The General Electric Company rev.2 28 April, 1989
COMMONWEALTH EDISON COMPANY QUAD CITIES STATION REQUALIFICATION QUESTION / ANSWER FORM Point Value: _.LfD._ Question # 7 - C-16 QUESTION C-16. State the two (2) conditions that can be used by the operator to base his decision on to stop driving control rods in this type of transient? (3.75)
ANSWER:
C-16. Any two answers required at 1.875 points each:
When all the rods are in to or beyond position 04.
When 537 pounds of Boron has been injected.
When the reactor is shutdown without boron, per the QNE. l f
REFERENCE:
QOA 300-15 MANUAL CONTROL ROD INSERTION FOLIDWING AN ATWS EVENT rev.1 OBJECTIVE:
TASK XREF: 200-05-01-020, Failure of reactor to scram when required or failure of control rods to fully insert during scram.
344-03-02-024, Direct corrective action to mitigate the consequences of the emergency event.
K/A XREF: 295037 SG-12 3.9/4.6 EST TIME: 3.1 minutes
[ddifEnddCCtPI 8AM W s .se can be reso wd A m'"d g d p lfw 'q the fast Lc mrO-PREPARED BY: Michael Orta DATE: ,_28 Aoril 1989 REVIEWED BY .__. DATE:
The General Electric Company rev.2 28 April, 1989
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.4 4-COMMONWEALTH ED:: SON COMPANY QUAD CITIES STATION REQUALIFICATION QUESTION / ANSWER FORM Point Value: 2.75 Question # 7 - C-20 i
QUESTION C-20. NOT SPECIFICALLY RELATED TO THE SCENARIO:
Explain why it is necessary to reduce recire pump speeds to minimum before they are tripped if the MSIVs are open and the turbine is on the line. (2.75)
ANSWER:
C-20. Recirc pump speed is reduced to minimize the RPV level transient so that when they are tripped the (steam capacity of the) turbio-is not lost due to a high level trip. (2.75)
J.
REFERENCE:
QGA 100-3 POWER CONTROL rev.2 OBJECTIVE:
TASK XREF: 200-05-01-020, Failure of reactor to scram when required or failure of control rods to fully insert
~
during scram.
344-03-02-024, Direct corrective actions to mitigate the consequences of the emergency event.
K/A XREF: 295037 EK3.01 4.1/4.2 SG-7 3.7/3.9 SG-12 3.9/4.6 ,
EST TIME: 1.8 minutes
~
DATE: 28 April 1989 PREPARED BY: Michael Orta DATE:
REVIEWED BY _
The General Electric Company rev.2 28 April, 1989
d
- l COMMONWEALTH EDISON COMPANY QUAD CITIES STATION REQUALIFICATION QUESTION / ANSWER FORM Point Value: _LJ_ Question # 7 - C-21 QUESTION ;
C-21. NOT SPECIFICALLY RELATED TO THE SCENARIO:
Assume that a loss of power occurred on MCC 14-1, which caused the Diesel Generator to start and load to MCC 14-1. The plant operator reports that the vent fan did not start due to a failure of the vent fan power supply breaker. Describe the corrective actions that would be taken to start the vent fan and the location where these would be performed? (3.5)
ANSWER: L C-21. 4 ou. ... r ,1-aa ou (C.07) ym. . ch Select the alternate power supply (1.75) in the U-1 Diesel generatc,r room (panel 2251-37) (1.75)
REFERENCE:
QOP 6600-4 rev.7 OBJECTIVE:
TASK XREF: 264-01-01-004 Monitor the Diesel Generator.
264-01-02-004, Monitor the Diesel Generator.
K/A XREF: 264000 K4.08 3.8/3.7 SG-1 3.7/4.2
' EST TIME: 2.9 minutes fg prohrn. ,
PREPARED BY: Michael Orta DATE: 28 Auril 1989 REVIEWED BY DATE:
The General Electric Company rev.2 28 April, 1989
. ,e
. I COMMONWEALTH EDISON COMPANY j I
QUAD CITIES STATION
. REQUALIFICATION QUESTION / ANSWER FORM f Point Value: 3.5 Question # 7 - S-1 QUESTION S-1. What, if any, State and Federal notifications must be made?
Include in your answer any applicable time requirements. (3.5)
ANSWER:
S-1. A NARS phone call would be made (.875), a call to the NRC (.875)
The NARS phone call must be made within 15 minutes of declaring the event (.875). The NRC phone call must be made within one (1) hour of declaring the event. (.875).
REFERENCE:
QEP 200-1 Classification of GSEP Condition rev.5 QEP 300-1 Notifications for GSEP Emergencies rev.1 OBJECTIVE:
TASK XREF: 344-03-02-020, Perform required notifications of on-site and off-site personnel for emergency events.
K/A XREF: 295037 SG-2 3.2/4.6 EST TIME: 3.0 minutes DATE: 28 April 1989 PREPARED BY: Michael Orta REVIEWED BY DATE: -
The General Electric Company rev.2 28 April, 1989
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COMMONWEALTH EDISON COMPAIN QUAD CITIES STATION
- REQUALIFICATION QUESTION / ANSWER FORM 1
Question #7 - Sd i Point Value: 2.00 I
1 QUESTION f
S-2. What, if any, GSEP classification is applicable for this 1 transient, include any EAL as relevant?. (2.0)
ANSWER:
A I S R T , f A L 1 2 0 0)
S-2. This event would be classified as an Site Energen:7 (in accordance with QLP 200-T1, EAL 12). M i
Dejete-INSTRUCTOR's NOTE: Th c scepirio is classified as a Site Emergency due to a failu 6f the RPS instrumentation to provide a scram, and because the etromatic reliefs lifted (A transient requiring operation of CCS h a Failure to SCRAM).
REFERENCE:
QEP 200-T1 Quat. Cities Emergency Action Levels, p. 5 rev.15 OBJECTIVE:
TASK XREF: 344-03-02-019, Classify emergency events requiring emergency plan implementation.
K/A XREF: 295037 SG-2 L2/4.6 EST TIME: 1.375 minutes k k G YN CQ&Cf,
$ is ws> GINN$ bat h be 0 b dW N YY!*a 094Nb N
$n (CCL gN40 r)lt0 h h4*t GCU4beb b* fNil oh i, %e prowe reld Je, d as an fccs cysh,n. hrebe
- he prope c!.JsAA is a,i Aket.
Tk quesWm also speci0t'0 h Lb0t the GAL.. $ int value has key an,i,,e/ & & pa.
DATE: 28 April 1989 PREPARED BY: Michael Orta REVIEWED BY DATE:
The General Electric Company rev.2 28 April, 1989
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